正常余热排出热交换器超流量运行分析  

Analysis of overflow operation of normal residual heat removal heat exchanger

作　　者：李经怀 龚震鑫 尤岩[1] 张菲茜 李波[1] 黄庆[1] LI Jinghuai;GONG Zhenxin;YOU Yan;ZHANG Feixi;LI Bo;HUANG Qing(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China)

机构地区：[1]上海核工程研究设计院股份有限公司,上海200233

出　　处：《压力容器》2024年第9期48-54,共7页Pressure Vessel Technology

基　　金：国家大型先进压水堆核电站重大专项(2010ZX06001002)。

摘　　要：针对核电厂调试过程中由于管道及节流件阻力以及流量分配变化导致的正常余热排出热交换器壳侧流量超出额定流量的问题,利用HTRI软件对120%流量下的热工和流致振动情况进行分析,其中间隙流速与临界流速比值最大为0.25(小于1),并且最大卡门旋涡振幅/管间隙最大值为0.04,小于判定准则中0.5的限值,结果表明120%流量下无流致振动风险;同时,热工计算时壳侧进口处流体密度和流速平方乘积(ρν^(2))超出标准限值要求,进一步采用有限元方法对拉杆和防冲挡板进行力学分析,分析结果表明,结构设计满足限值要求。实际工程调试过程中,设备在120%流量工况下,仍然能够安全运行。综合分析,该正常余热排出热交换器壳侧在超20%设计流量时,工程上能够满足要求。For the problem that the shell side flow of normal residual heat removal heat exchanger exceeds the nominal flow rate due to flow distribution changes during the commissioning process of nuclear power plants,HTRI was used to analyze the thermal and flow induced vibration conditions at 120%flow rate.The maximum ratio of gap velocity to critical velocity was 0.25,which is less than 1.The max.vortex shedding amplitude to tube gap was 0.04,which is less than the 0.5.The above results indicate that there is no flow induced vibration risk at 120%flow rate.However,theρν^(2)at the inlet of the shell side exceeded the limit requirements in the standard.Therefore,the finite element method was further used to perform mechanical analysis on the impingement plate and tie rods.The analysis results show that the structural design meets the strength requirements.In the actual engineering commissioning process,the equipment still can operate safely under the condition of 120%flow rate.Through comprehensive analysis,the flow rate on the shell side of the normal residual heat removal heat exchanger can meet the engineering requirements when it exceeds nominal design flow by 20%.

关 键 词：热交换器 正常余热排出系统 热工分析 振动分析 力学分析 

分 类 号：TH49[机械工程—机械制造及自动化] TL38[核科学技术—核技术及应用]